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Colin Judge: Testing structural materials in Idaho’s newest hot cell facility
Idaho National Laboratory’s newest facility—the Sample Preparation Laboratory (SPL)—sits across the road from the Hot Fuel Examination Facility (HFEF), which started operating in 1975. SPL will host the first new hot cells at INL’s Materials and Fuels Complex (MFC) in 50 years, giving INL researchers and partners new flexibility to test the structural properties of irradiated materials fresh from the Advanced Test Reactor (ATR) or from a partner’s facility.
Materials meant to withstand extreme conditions in fission or fusion power plants must be tested under similar conditions and pushed past their breaking points so performance and limitations can be understood and improved. Once irradiated, materials samples can be cut down to size in SPL and packaged for testing in other facilities at INL or other national laboratories, commercial labs, or universities. But they can also be subjected to extreme thermal or corrosive conditions and mechanical testing right in SPL, explains Colin Judge, who, as INL’s division director for nuclear materials performance, oversees SPL and other facilities at the MFC.
SPL won’t go “hot” until January 2026, but Judge spoke with NN staff writer Susan Gallier about its capabilities as his team was moving instruments into the new facility.
André L. Rogister
Fusion Science and Technology | Volume 41 | Number 2 | March 2002 | Pages 251-267
Transport and Instabilities | doi.org/10.13182/FST02-A11963524
Articles are hosted by Taylor and Francis Online.
Energy and particle transport rates in magnetically confined plasmas are often larger than neo-classical transport owing to binary collisions would allow. Anomalous transport, a major road block on the path to an economic fusion reactor, is a consequence of electric and magnetic fluctuations driven to supra thermal levels by various instability mechanisms. The linearly excited modes saturate by inducing a relaxation of the equilibrium profiles towards the marginally stable state, on the one hand, and via various non-linear interaction mechanisms, on the other hand. Specific instabilities, profile relaxation and non-linear interaction models are described and their successes and drawbacks are analysed in the light of observed characteristics of plasma confinement. A rough evaluation of the nuclear heating power required to balance the anomalous losses in the International Tokamak Experimental Reactor (ITER) is derived on the basis of the very qualitative mixing length estimate applied to electrostatic drift wave turbulence. Results from large-scale gyro-kinetic simulation codes are discussed.